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Letter, Technical Specifications  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

ANSI 18.1 +  and ANSI N18.1-1971 +

Boron +, Iodine +, Uranium +, Xenon +, Lead +, Tin +, Plutonium +  and Samarium +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1302 +, 10 CFR 50.3 +, 10 CFR 50.4 +, 10 CFR 50.90 +, 10 CFR 70.3, License Requirements +, 10 CFR 50.36a +, 10 CFR 50.54#o +, 10 CFR 50.91#a +  and 10 CFR 50.71#e +

05000346  +  and 00346  +

70 FR 24126 +  and 70 FR 10298 +

FirstEnergy +  and Bezilla M +

ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +, ML061560134 +  and ML061560134 +

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

Tritium +  and Iodine-131 +

NUREG-1430 +, NUREG-01 +, NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing +  and NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +

Regulatory Guide 1.163 +, Regulatory Guide 1.45 +, Regulatory Guide 1.52 +, Regulatory Guide 1.33 +, Regulatory Guide 1.121 +  and Regulatory Guide 1.8 +

SR-3.4.13.1 +, SR-4.0.3 +, SR-4.0.2 +, SR-3.4.13.2 +, SR-4.7.9 +, SR-4.4.5.1 +, SR-4.4.5.2 +, SR-4.1.1.1.1 +, SR-4.4.6.2.1 +, SR-4.4.6.2 +, SR-4.4.5.0 +, SR-4.4.5.9 +, SR-4.4.5.8 +  and SR-4.4.5.7 +

Ohio +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Control Room Emergency Ventilation +, Shield Building +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.13 +, TS-3.4.5 +, TS-3.4.6.2 +, TS-3.4.1.2 +, TS-3.7.9 +, TS-3.1.1 +, TS-4.4.5.4 +, TS-3.1.1.1 +, TS-6.0 +, TS-6.9.1 +, TS-3.7.18 +, TS-6.8.4.g +, TS-3.4.4.1 +, TS-6.9.1.5 +, TS-4.4.5.9 +, TS-4.4.5.7 +  and TS-4.4.5.8 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Shutdown Margin +, Packing leak +, High Radiation Area +, Ultimate heat sink +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Operating Basis Earthquake +, Nondestructive Examination +, Incorporated by reference +, Locked High Radiation Area +, Shift Technical Advisor +, Annual Radiological Environmental Operating Report +, Process Control Program +, Stress corrosion cracking +, Pressure Boundary Leakage +, Fire Protection Program +, Unidentified leakage +, Eddy-Current Testing +  and Operational leakage +